Dislocation-defect interactions in nuclear reactor pressure-vessel steels investigated by means of internal friction
A study of pressure-vessel steel embrittlement mechanisms by means of temperature-dependent and amplitude-dependent internal friction has been carried out within the framework of commercial surveillance of nuclear reactor components. An inverted torsion pendulum operating at ∼1 Hz has been employed...
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Published in | Journal of alloys and compounds Vol. 310; no. 1; pp. 445 - 448 |
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Main Authors | , , |
Format | Journal Article Conference Proceeding |
Language | English |
Published |
Lausanne
Elsevier B.V
28.09.2000
Elsevier |
Subjects | |
Online Access | Get full text |
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Summary: | A study of pressure-vessel steel embrittlement mechanisms by means of temperature-dependent and amplitude-dependent internal friction has been carried out within the framework of commercial surveillance of nuclear reactor components. An inverted torsion pendulum operating at ∼1 Hz has been employed to study a wide variety of pressure-vessel steels and an IAEA reference material in various conditions. This contribution will discuss the results for the JRQ reference material only and serve as a basis on which to interpret the data from real pressure-vessel steels. The temperature-dependent experiments evidence a reduction in the dislocation mobility as a result of neutron irradiation and prove that the technique is sensitive to thermal ageing involving changes in the dislocation mobility and type of dislocation-defect interaction. Amplitude-dependent internal friction provides a means to determine the yield strength of the material. The importance of the influence of dislocation dragging on the yield stress is highlighted. |
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ISSN: | 0925-8388 1873-4669 |
DOI: | 10.1016/S0925-8388(00)00955-5 |